Letter Sequence Meeting |
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EPID:L-2020-LRM-0009, Summary of January 27, 2020, Public Meeting with Tennessee Valley Authority Regarding the Future Submittal of Steam Generator Tube Inspection Related License Amendment Request (Open) |
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MONTHYEARML20024D2112020-01-27027 January 2020 Pre-Submittal Meeting for License Amendment Request (LAR) Revised Steam Generator (SG) Inspection Intervals - January 27, 2020 Project stage: Meeting ML20035C8942020-01-27027 January 2020, 12 February 2020 Summary of January 27, 2020, Public Meeting with Tennessee Valley Authority Regarding the Future Submittal of Steam Generator Tube Inspection Related License Amendment Request Project stage: Request ML20035C8192020-02-12012 February 2020 Summary of January 27, 2020, Public Meeting with Tennessee Valley Authority Regarding the Future Submittal of Steam Generator Tube Inspection Related License Amendment Request Project stage: Meeting ML20049G1822020-02-18018 February 2020 February 20, 2020 - Pre-submittal Meeting Presentation - Transition to Westinghouse Fuel Project stage: Meeting ML20050C8662020-02-20020 February 2020 February 20, 2020 - Pre-Submittal Meeting Presentation - Permanent Operation with Control Rod H8 Removed Project stage: Meeting ML20055C2312020-03-0505 March 2020 Summary of February 20, 2020 Pre-submittal Meeting - Operation Without Control Rod H8 and Fuel Transition Project stage: Meeting 2020-02-18
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Category:Meeting Briefing Package/Handouts
MONTHYEARML24312A1432024-11-0707 November 2024 SDP for Nextera RUG Meeting - 11.7.2024 - Rev. 0 ML24312A0532024-11-0707 November 2024 FLEX HP Pump SDP for Nextera RUG Meeting - 11.7.2024 - Rev. 0 ML24284A0042024-10-16016 October 2024 Application to Use Online Monitoring Methodology for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant Session Slides ML24228A2312024-08-15015 August 2024 TVA Meeting Slides for August 19 Public Meeting Re QAPD Supplement ML24225A2542024-08-14014 August 2024 August 14, 2024 - TVA Pre-Sub Meeting Presentation - Sequoyah, Units 1 and 2; Watts Bar, Units 1 and 2 - License Amendment Request to Revise TS 3.5.2 ECCS - Operating ML24191A0642024-07-16016 July 2024 TVA Pre-Submittal Conference Presentation for Proposed LAR Regarding a Revision to Sequoyah Fuel Handling Accident Analysis, Deletion of TS 3.9.4 and Modification of TS 3.3.6 - July 16, 2024 ML24149A1332024-05-29029 May 2024 Pre-Submittal Meeting for Proposed License Amendment Regarding Hydrologic Analysis Updates Public Portion Meeting Slides ML24137A2872024-05-16016 May 2024 Pre-Submittal Meetingfor Proposed License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources - Operating to Clarify Requirements for Diesel Generator Testing ML24127A0412024-05-0606 May 2024 May 6, 2024 Meeting Slides ML24117A0352024-05-0202 May 2024 TVA Sequoyah Nuclear Plant - 1B Emergency Diesel Generator Regulatory Conference May 02, 2024 -Presentation Slides ML24113A0962024-04-22022 April 2024 RIPE Pre-Submittal Meeting Slides ML24078A2722024-04-10010 April 2024 Subsequent License Renewal Public Scoping Meeting ML24067A2832024-03-27027 March 2024 2023 Browns Ferry, Sequoyah and Watts Bar Annual Assessment Public Meeting Presentation Slides ML24082A2532024-03-26026 March 2024 Summary of March 18, 2024, Public Preapplication Meeting with Tennessee Valley Authority Regarding a Future License Amendment Request Related to Fuel Handling and Fuel Decay Time ML24044A0872024-02-14014 February 2024 TVA Slides - Watts Bar Nuclear Plant Pre-Submittal Meeting for License Amendment Request to Revise TS 3.7.11, Main Control Room Area Chilled Water System ML24037A0252024-02-0808 February 2024 Pre-Submittal Presentation - 02/08/2024 - Proposed License Amendment Request Change to the Sequoyah Nuclear Plant Technical Specifications 3.8.1 and 3.8.2 ML24032A2752024-02-0707 February 2024 Pre-Pre-Submittal Meeting for Proposed License Amendment Regarding Hydrologic Analysis Updates (Slides) ML24019A1512024-01-22022 January 2024 Slides - Modification of Browns Ferry Technical Specifications to Eliminate LCO 3.3.2.1 Actions C.2.1.1 and C.2.1.2 for Rod Worth ML23345A1662023-12-13013 December 2023 Tennessee Valley Authority - Pre-submittal Meeting for Conversion of Nuclear Quality Assurance Plan from ANSI N45.2-1971 to ASME NQA-1-2015 (EPID L-2023-LRM-0103) - Slides ML23291A1562023-10-18018 October 2023 NRC Pre-Submittal Meeting Watts Bar & Sequoyah LAR, TVA Presentation Slides ML23264A0412023-09-27027 September 2023 NRC Pre-Submittal Meeting WBN Rebaseline LAR, TVA Presentation Slides ML23251A1252023-09-12012 September 2023 Pre-submittal Meeting for License Amendment Request, Modify the Watts Bar Nuclear Plant Unit 1 and Unit 2 Technical Specification Surveillance Requirement 3.9.5.1 ML23251A1212023-09-12012 September 2023 RHR Flow Rate Reduction During Mode 6 Operation at 23 Ft. Refueling Water Level Technical Specification Change NON-PROPRIETARY Slides ML23178A0832023-07-10010 July 2023 Pre-submittal Meeting Slides for License Amendment Request to Revise Technical Specification Table 1.1-1 Regarding the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs ML23130A0922023-05-11011 May 2023 NRC Browns Ferry Nuclear Plant, Units 1, 2, and 3, Subsequent License Renewal Application, Public Meeting Slides ML23130A0912023-05-11011 May 2023 TVA Browns Ferry Nuclear Plant Safety Pre-Application Public Meeting Slides 05/11/2023 ML23128A2882023-05-0808 May 2023 TVA Nuclear Plants -2022 EOC Media Slides ML23052A0362023-02-22022 February 2023 February 22, 2023, Pre-Submittal Meeting for the License Amendment Request for Increased Tritium Production at Watts Bar (EPID L-2023-LRM-0010) - Meeting Slides ML23044A5182023-02-15015 February 2023 Pre-Submittal Meeting Slides for Expedited License Amendment Request Re Main Control Room Chiller Completion Time Extension ML23041A3562023-02-15015 February 2023 February 15, 2023 Pre-submittal Meeting for Expedited License Amendment Request Main Control Room (MCR) Chiller Completion Time Extension (EPID L-2022-LRM-0098) (Slides) ML23025A0472023-01-25025 January 2023 Pre-Submittal Meeting for Proposed License Amendment Request Regarding Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves - January 25, 2023 ML22318A1042022-11-14014 November 2022 Pre-submittal Meeting for American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative WBN-2-ISI-01 Slide Presentation ML22285A1902022-10-13013 October 2022 October 13, 2022 Public Meeting on 5th Interval Alternative Planned Requests - Licensee Slides ML22277A6562022-10-0606 October 2022 Subsequent License Renewal Application - SAMA Pre-Application Meeting October, 2022 (TVA Slides) ML22279A8992022-10-0606 October 2022 Subsequent License Renewal Application - SAMA Pre-Application Meeting October 6, 2022-TVA Slides ML22264A2332022-09-22022 September 2022 Slides for Pre-Submittal Meeting for Request to Use a Later Edition of the ASME OM Code for the Fifth Inservice Testing (IST) 10-Year Interval ML22157A4132022-06-0606 June 2022 Plants - Pre-Submittal Teleconference for Proposed Amendment Request Regarding the Change for the Sequoyah and Watts Bar Nuclear Plants Technical Specification 3.4.12 Meeting Slides ML22102A3032022-04-12012 April 2022 Pre-submittal Meeting for Request for Exemption from Requirements of 10 CFR 26.205(d)(4) and 10 CFR 26.205(d)(6) Slide Presentation ML22080A1662022-03-21021 March 2022 TVA Nuclear Plants -2021 EOC Media Loop Slides for Automatic Play ML21343A0282021-12-14014 December 2021 TVA Slide Presentation Regarding Pre-Submittal Meeting for Proposed Revision to Capsule Withdrawal Schedule ML21308A4932021-11-0808 November 2021 Pre-submittal Meeting Presentation - License Amendment Request to Revise Sequoyah Operating License to Use Fire and Seismic PRA Models for 10 CFR 50.69 Risk-Informed Categorizations (EPID L-2021-LRM-0109) (Slides) ML21281A2282021-10-13013 October 2021 Tennessee Valley Authority Fleet Pre-Submittal Meeting for License Amendment Request to Change Emergency Action Level Scheme Presentation - October 13, 2021 (EPID L-2021-LRM-0096) (Slides) ML21270A0322021-09-27027 September 2021 Presentation Slides for Browns Ferry Pre-submittal Public Meeting September 27, 2021 ML21265A0422021-09-21021 September 2021 Presentation Slides for Browns Ferry Pre-submittal Public Meeting 09/22/2021 ML21252A3632021-09-15015 September 2021 Pre-Submittal Meeting for License Amendment Request to Eliminate the High Negative Flux Rate Trip ML21250A3652021-09-0808 September 2021 Meeting Slides - Watts Bar Nuclear Plant Unit 2, Presubmittal Teleconference for Proposed License Amendment to Revise the Updated Final Safety Analyses Report (UFSAR) to Use a Tube Support Plate Locking/Displacement Analysis ML21250A3012021-09-0707 September 2021 TVA Slides for September 7, 2021, Presubmittal Meeting to Discuss Planned Browns Ferry TSTF-505 License Amendment Request ML21229A1992021-08-19019 August 2021 Mid-Cycle SG Outage Strategy (EPID L-2021-LRM-0067) (Slides) ML21217A2872021-08-19019 August 2021 TVA Slides - Pre-Submittal Meeting for Proposed License Amendment Request Re Application to Modify Technical Specification 3.7.8 Essential Raw Cooling Water (ERCW) System, to Support Permanent Shutdown Board ML21231A0972021-08-18018 August 2021 TVA Slides - Pre-Submittal Meeting for Proposed LAR Regarding Application to Modify Watts Bar Units 1 and 2 Technical Specification 3.7.8, Essential Raw Cooling Water (ERCW) System, to Support Permanent Shutdown Board Cleaning 2024-08-15
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24311A0332024-11-0707 November 2024 TVA Pre-Submittal Meeting Presentation on License Amendment Request to Revise SR 3.4.14.1 Reactor Coolant System Pressure Isolation Valves Leakage Testing Frequency on November 7, 2024 ML24312A1432024-11-0707 November 2024 SDP for Nextera RUG Meeting - 11.7.2024 - Rev. 0 ML24312A0532024-11-0707 November 2024 FLEX HP Pump SDP for Nextera RUG Meeting - 11.7.2024 - Rev. 0 ML24284A0042024-10-16016 October 2024 Application to Use Online Monitoring Methodology for the Sequoyah Nuclear Plant and Watts Bar Nuclear Plant Session Slides ML24228A2312024-08-15015 August 2024 TVA Meeting Slides for August 19 Public Meeting Re QAPD Supplement ML24225A2542024-08-14014 August 2024 August 14, 2024 - TVA Pre-Sub Meeting Presentation - Sequoyah, Units 1 and 2; Watts Bar, Units 1 and 2 - License Amendment Request to Revise TS 3.5.2 ECCS - Operating ML24191A0642024-07-16016 July 2024 TVA Pre-Submittal Conference Presentation for Proposed LAR Regarding a Revision to Sequoyah Fuel Handling Accident Analysis, Deletion of TS 3.9.4 and Modification of TS 3.3.6 - July 16, 2024 ML24184B9162024-07-10010 July 2024 U.S. NRC Meeting Slides for Meeting with Tennessee Valley Authority Regarding NRC Questions Regarding Scope of Nuclear Quality Assurance Program ML24149A1332024-05-29029 May 2024 Pre-Submittal Meeting for Proposed License Amendment Regarding Hydrologic Analysis Updates Public Portion Meeting Slides ML24137A2872024-05-16016 May 2024 Pre-Submittal Meetingfor Proposed License Amendment Request for Adoption of Technical Specification Task Force Traveler TSTF-276-A, Revision 2, Regarding TS 3.8.1 AC Sources - Operating to Clarify Requirements for Diesel Generator Testing ML24127A0412024-05-0606 May 2024 May 6, 2024 Meeting Slides ML24117A0352024-05-0202 May 2024 TVA Sequoyah Nuclear Plant - 1B Emergency Diesel Generator Regulatory Conference May 02, 2024 -Presentation Slides ML24113A0962024-04-22022 April 2024 RIPE Pre-Submittal Meeting Slides ML24078A2722024-04-10010 April 2024 Subsequent License Renewal Public Scoping Meeting ML24067A2832024-03-27027 March 2024 2023 Browns Ferry, Sequoyah and Watts Bar Annual Assessment Public Meeting Presentation Slides ML24051A2042024-02-20020 February 2024 Tennessee Valley Authority Pre-Sub Meeting Presentation 2-22-2024 Pmns 20240113 ML24037A0252024-02-0808 February 2024 Pre-Submittal Presentation - 02/08/2024 - Proposed License Amendment Request Change to the Sequoyah Nuclear Plant Technical Specifications 3.8.1 and 3.8.2 ML24032A2752024-02-0707 February 2024 Pre-Pre-Submittal Meeting for Proposed License Amendment Regarding Hydrologic Analysis Updates (Slides) ML24019A1512024-01-22022 January 2024 Slides - Modification of Browns Ferry Technical Specifications to Eliminate LCO 3.3.2.1 Actions C.2.1.1 and C.2.1.2 for Rod Worth ML23345A1662023-12-13013 December 2023 Tennessee Valley Authority - Pre-submittal Meeting for Conversion of Nuclear Quality Assurance Plan from ANSI N45.2-1971 to ASME NQA-1-2015 (EPID L-2023-LRM-0103) - Slides ML23291A1562023-10-18018 October 2023 NRC Pre-Submittal Meeting Watts Bar & Sequoyah LAR, TVA Presentation Slides ML23264A0412023-09-27027 September 2023 NRC Pre-Submittal Meeting WBN Rebaseline LAR, TVA Presentation Slides ML23251A1252023-09-12012 September 2023 Pre-submittal Meeting for License Amendment Request, Modify the Watts Bar Nuclear Plant Unit 1 and Unit 2 Technical Specification Surveillance Requirement 3.9.5.1 ML23251A1212023-09-12012 September 2023 RHR Flow Rate Reduction During Mode 6 Operation at 23 Ft. Refueling Water Level Technical Specification Change NON-PROPRIETARY Slides ML23178A0832023-07-10010 July 2023 Pre-submittal Meeting Slides for License Amendment Request to Revise Technical Specification Table 1.1-1 Regarding the Required Number of Fully Tensioned Reactor Pressure Vessel Head Closure Studs ML23130A0922023-05-11011 May 2023 NRC Browns Ferry Nuclear Plant, Units 1, 2, and 3, Subsequent License Renewal Application, Public Meeting Slides ML23130A0332023-05-11011 May 2023 NRC Presentation Browns Ferry Subsequent License Renewal Pre-application Meeting, Environmental Overview ML23130A0912023-05-11011 May 2023 TVA Browns Ferry Nuclear Plant Safety Pre-Application Public Meeting Slides 05/11/2023 ML23130A0302023-05-10010 May 2023 TVA Presentation Browns Ferry Nuclear Plant Subsequent License Renewal License Application – Environmental Report ML23128A2882023-05-0808 May 2023 TVA Nuclear Plants -2022 EOC Media Slides ML23052A0362023-02-22022 February 2023 February 22, 2023, Pre-Submittal Meeting for the License Amendment Request for Increased Tritium Production at Watts Bar (EPID L-2023-LRM-0010) - Meeting Slides ML23044A5182023-02-15015 February 2023 Pre-Submittal Meeting Slides for Expedited License Amendment Request Re Main Control Room Chiller Completion Time Extension ML23041A3562023-02-15015 February 2023 February 15, 2023 Pre-submittal Meeting for Expedited License Amendment Request Main Control Room (MCR) Chiller Completion Time Extension (EPID L-2022-LRM-0098) (Slides) ML23025A0472023-01-25025 January 2023 Pre-Submittal Meeting for Proposed License Amendment Request Regarding Technical Specification Surveillance Requirements 3.4.3.2 and 3.5.1.11 Regarding Safety Relief Valves - January 25, 2023 ML23010A2542023-01-12012 January 2023 Pre-submittal Meeting for Expedited License Amendment Request Main Control Room (MCR) Chiller Completion Time Extension -- Meeting Slides ML22318A1042022-11-14014 November 2022 Pre-submittal Meeting for American Society of Mechanical Engineers Boiler and Pressure Vessel Code Section XI, Request for Alternative WBN-2-ISI-01 Slide Presentation ML22285A1902022-10-13013 October 2022 October 13, 2022 Public Meeting on 5th Interval Alternative Planned Requests - Licensee Slides ML22277A6562022-10-0606 October 2022 Subsequent License Renewal Application - SAMA Pre-Application Meeting October, 2022 (TVA Slides) ML22279A8992022-10-0606 October 2022 Subsequent License Renewal Application - SAMA Pre-Application Meeting October 6, 2022-TVA Slides ML22264A2332022-09-22022 September 2022 Slides for Pre-Submittal Meeting for Request to Use a Later Edition of the ASME OM Code for the Fifth Inservice Testing (IST) 10-Year Interval ML22201A1262022-07-20020 July 2022 July 20, 2022 - Pre-submittal Meeting for Inservice Testing (IST) Program Request for Alternative for the Centrifugal Charging Pump 1B-B Testing Per ISTB-3310 (RP-12) ML22157A4132022-06-0606 June 2022 Plants - Pre-Submittal Teleconference for Proposed Amendment Request Regarding the Change for the Sequoyah and Watts Bar Nuclear Plants Technical Specification 3.4.12 Meeting Slides ML22103A0852022-04-14014 April 2022 And Watts Bar Plant Pre-submittal Meeting for Inservice Testing (IST) Program Request for Alternative for the Motor Driven Auxiliary Feedwater Pump Testing Following Maintenance During an Outage Per ISTB-3310 ML22102A3032022-04-12012 April 2022 Pre-submittal Meeting for Request for Exemption from Requirements of 10 CFR 26.205(d)(4) and 10 CFR 26.205(d)(6) Slide Presentation ML22080A1662022-03-21021 March 2022 TVA Nuclear Plants -2021 EOC Media Loop Slides for Automatic Play ML22046A2932022-02-15015 February 2022 Pre-submittal Meeting Presentation - Request for Alternative to ASME OM Code ISTC-3630 Regarding Leakage of Pressure Isolation Valves ML22035A0002022-02-0404 February 2022 February 8, 2022, Pre-Submittal Meeting Slides Regarding Proposed Change to Modify the Allowable Value for Technical Specification Table 3.3.2-1, Function 6.e(1) ML22013A6432022-01-19019 January 2022 TVA Slides - Watts Bar Nuclear Plant (WBN) Schedule for the Development of a License Amendment Request (LAR) for Increased Tritium Production at WBN ML21343A0282021-12-14014 December 2021 TVA Slide Presentation Regarding Pre-Submittal Meeting for Proposed Revision to Capsule Withdrawal Schedule ML21308A4932021-11-0808 November 2021 Pre-submittal Meeting Presentation - License Amendment Request to Revise Sequoyah Operating License to Use Fire and Seismic PRA Models for 10 CFR 50.69 Risk-Informed Categorizations (EPID L-2021-LRM-0109) (Slides) 2024-08-15
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Discussion of License Amendment Request for Sequoyah Nuclear Plant Units 1 & 2 -
Fuel Transition Pre-Submittal Follow-up Meeting February 20, 2020
Introductions
- Kim Hulvey and Gordon Williams - TVA Licensing
- David Brown- TVA General Manager, Reactor Engineering and Fuels
- Chris Carey and Kasey Decker - TVA Nuclear Safety Analysis
- Westinghouse (on the Phone) -Individuals will introduce themselves when answering questions l 2
Objectives
- Nov. 2018 meeting and approach changes
- Discuss planned submittal and need date
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Background===
- Feedback from the NRC on the November 2018 approach - To independently verify that proposed TS changes meet applicable requirements and design criteria, and that proposed analysis methods are applicable and properly implemented, analytic results for the proposed fuel design need to be included in the fuel transition LAR (Reference ML19031A150)
- Scope has been expanded to incorporate feedback HTP is a trademark or registered trademark of Framatome or its affiliates, in the United States and other countries l 4
Revised Content of LAR
- Safety Analyses have been performed for the RFA-2 fuel using approved WEC methods and will be summarized
- Impacted UFSAR Chapter 15 events updated to WEC methods and guidance
- Representative designs for the transition core (mixed core of HTP & RFA-2) and equilibrium core (RFA-2 only)
- Compatibility of the HTP and RFA-2 in a mixed core will be discussed
- The approach for setting safety limits on the HTP and RFA-2 fuel in the transition cores will be presented l 5
Requested Technical Specification Changes
- Add Optimized ZIRLOTM cladding to the approved fuel clad materials (TS 4.2.1)
- Move the Core Safety Limits Figure, OTDT/OPDT and time delay constants, and RCS DNB Limits to the Core Operating Limits Report (COLR) - (consistent with TSTF-339, R2)
- Revise the DNB limit to reflect WRB-2M correlation application
- Revise the fuel centerline temperature limit consistent with the approved PAD5 methodology Optimized ZIRLO is a trademark or registered trademark of Westinghouse Electric Company LLC, its affiliates and/or its subsidiaries in the United States of America and may be registered in other countries throughout the world. All rights reserved. Unauthorized use is strictly prohibited. Other names may be trademarks of their respective owners.
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Requested Technical Specification Changes (continued)
- Revise the Power Distribution Limits (TSs 3.2) to be consistent with WEC methodology and NRC-approved WCAP-17661-P-A, Revision 1
- Applied changes to reflect the installation and use of BEACONTM-TSM
- Replace Framatome methods with WEC methods in the Core Operating Limits Report Methodologies list (TS 5.6.3)
- Permanent removal of RCCA H-08 and associated drive shaft for Unit 1 (TS 4.2.2)
BEACONTM-TSM is a trademark or registered trademark of Westinghouse Electric Company, LLC, its affiliates and/or subsidiaries in the United States of America and may be registered in other countries throughout the world. All rights reserved. Unauthorized use is strictly prohibited. Other names may be trademarks of their respective owners l 7
Additional Documents to be Included in LAR
- TS Bases - Unit 1 - for information
- Representative COLR - Unit 1 - for information
- TRM changes to reflect BEACON application
- FULL SPECTRUMTM LOCA (FSLOCATM)
Evaluation Model (EM) application to Sequoyah
- 10 CFR 50.46 Exemption Request for Optimized ZIRLO FULL SPECTRUMTM and FSLOCATM are trademarks or registered trademarks of Westinghouse Electric Company, LLC, its affiliates and/or subsidiaries in the United States of America and may be registered in other countries throughout the world. All rights reserved. Unauthorized use is strictly prohibited. Other names may be trademarks of their respective owners.
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Analysis Approach for the HTP Fuel
- Framatome provided WEC with data regarding the HTP fuel and core designs
- WEC nuclear design methods have been used to model prior HTP cycles
- The power distribution information has been used to establish peaking limits for the HTP fuel
- Because previous HTP peaking limits were developed using approved Framatome methods, maintaining HTP peaking limits to that seen in previous HTP cores offers conformance with those methods l 9
Analysis Approach for the HTPTM Fuel (continued)
- The COLR limit for FQ(Z) will be unchanged from the current limit for the HTP fuel
- The FNH COLR limit will be set separately for RFA-2 and HTP fuel
- The HTP fuel will be monitored to a lower limit using BEACON-TSM
- HTP fuel rod mechanical design and fuel performance will be confirmed by ensuring operation within the previously established acceptable operating envelopes l 10
Analysis Approach for the HTP Fuel (continued)
- Sufficient information has been obtained from Framatome to assess the HTP fuel for the following analyses:
- Thermal-Hydraulic behavior and compatibility
- Non-LOCA safety analyses will use PAD5 generated fuel temperatures to assess HTP
- LOCA analysis with a transition core PCT penalty assessment for HTP fuel
- Seismic/LOCA grid crush
- Transition core DNBR penalty for the HTP fuel is determined by approved WEC transition core methodology and conservative assumptions on the HTP l 11
Proposed Schedule for Submittal and Requested Approval
- SQN plans to load WEC RFA-2 fuel in the fall of 2022
- TVA will submit the LAR by June 2020
- In order to proceed with confidence with the transition to RFA-2, TVA requests LAR approval by June 2021 l 12
Closing and Questions l 13